A model reproducing strain softening behavior in ceramic materials is proposed, base on a critical treatment of previous mechanical experimental results on uranium dioxide. The main hypothesis is that the strain softening ...

Uranium dioxide is the standard nuclear fuel for pressurized water reactors in France. This ceramic is manufactured by sintering. The standard shape for use in nuclear reactor is a small cylinder, also called “pellet”, ...

Development and evolution of compressive residual stress during nitriding treatment are studied. A model carbon iron-based alloy Fe-3wt.%Cr-0.35wt.%C was nitrided in gas at 550 °C for different times. Microstructural ...